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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Hiromi Kanbe, Tadashi Inoue, Toshi Tomizawa, Hiroaki Kōyama, Hiroharu Itami
Nuclear Technology | Volume 60 | Number 3 | March 1983 | Pages 367-378
Technical Paper | LWR Control Materials—I and II / Fission Reactor | doi.org/10.13182/NT83-A33124
Articles are hosted by Taylor and Francis Online.
The characterization of radioactive corrosion pro-ducts and the distribution of 60Co on specimens taken from the Pipe of the Ōarai Water Loop of the Japan Material Testing Reactor, with and without decontamination, were investigated. The corrosion product layer was classified in two categories, i.e., a soft crud layer and a hard crud layer. The former is the layer where corrosion products in the water are deposited and the latter is the corroded layer of base material of the pipe. The main chemical states of both layers were α-Fe2O3 and Fe3O4 in equivalent amounts. The 60Co in the corrosion products was considered to be absorbed into the magnetite. Grain boundary diffusion was suggested as a transport mechanism for penetration into the base material. It was found that soft and hard cruds must be removed to get a high decontamination factor.